1-6 of 6
Guoliang Zhang
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Proceedings Papers

Study on the Influence of Roughness on Fuel Rod Gap Heat Transfer

Weichao Liu, Guoliang Zhang, Changzheng Li, Jin Cao, Shaofang Lin, Xiangang Fu, Lihong Nie, Yongjun Deng
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A060, August 8–12, 2022
Paper No: ICONE29-93004
DOI: https://doi.org/10.1115/ICONE29-93004
View Paper
PDF
Topics: Cladding systems (Building), Fuel rods, Heat transfer, Heat transfer coefficients, Surface roughness
Proceedings Papers

Analysis of the Influence of RCCA Swelling on Rod Falling and Study on Mitigation Measures

Zhipeng Lv, Guoliang Zhang, Changzheng Li, Weichao Liu, Shaofang Lin, Lihong Nie, Zhijun Li, Anlong Zhang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A067, August 8–12, 2022
Paper No: ICONE29-93095
DOI: https://doi.org/10.1115/ICONE29-93095
View Paper
PDF
Topics: Absorption, Cladding systems (Building), Deformation, Design, Irradiation (Radiation exposure), Neutrons, Pressurized water reactors, Rods, Safety, Shock absorbers
Proceedings Papers

Study of Iodine-Induced Stress Corrosion Cracking of CZ2 Alloy

Lin Shi, Changyuan Gao, Guoliang Zhang, Guocheng Sun, Xu Wang, Liutao Chen, Jun Tan
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A091, August 8–12, 2022
Paper No: ICONE29-93835
DOI: https://doi.org/10.1115/ICONE29-93835
View Paper
PDF
Topics: Alloys, Fracture (Materials), Fracture (Process), Stress corrosion cracking
Proceedings Papers

Study on Out-Pile Performance of CZ Zirconium Alloy Guide Tube

Changyuan Gao, Lin Shi, Guoliang Zhang, Yang Xu, Minli Chen, Liutao Chen, Jun Tan
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A089, August 8–12, 2022
Paper No: ICONE29-93816
DOI: https://doi.org/10.1115/ICONE29-93816
View Paper
PDF
Topics: Corrosion, Creep, Zirconium alloys, Alloys, Zirconium, Corrosion resistance, Stress, Temperature, Mechanical testing, Particulate matter
Proceedings Papers

Oxidation Behaviour of CZ Alloys Under High Temperature Steam

Minli Chen, Changyuan Gao, Guoliang Zhang, Lin Shi, Liutao Chen, Jun Tan
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A087, August 8–12, 2022
Paper No: ICONE29-93795
DOI: https://doi.org/10.1115/ICONE29-93795
View Paper
PDF
Topics: Alloys, High temperature steam, Oxidation, Steam, Zirconium alloys
Proceedings Papers

Modeling of Fuel Rod Behavior and Recent Advances of the JASMINE Code

Xiaoyan Wei, Xin Jin, Yongjun Deng, Guoliang Zhang, Xiangang Fu
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A043, July 2–6, 2017
Paper No: ICONE25-67144
DOI: https://doi.org/10.1115/ICONE25-67144
View Paper
PDF
Topics: Fuel rods, Modeling, China, Computer software, Nuclear power, Nuclear reactors